PSI - Issue 17

Available online at www.sciencedirect.com Structural Int grity Procedia 00 (2019) 000 – 000 Available online at www.sciencedirect.com ScienceDirect Structural Integrity Procedia 00 (2019) 000 – 000 Available online at www.sciencedirect.com ScienceDirect

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Procedia Structural Integrity 17 (2019) 123–130

ICSI 2019 The 3rd International Conference on Structural Integrity Numerical analysis of the BWR-5 beltline region containing a crack postulated for an extended period of operation Salatiel Pérez Montejo a , Pablo Ruiz López b , Gilberto Soto Mendoza a , Alejandra Armenta Molina a , Abraham Villanueva García a , Luis H. Hernández Gómez a,* a Instituto Politécnico Nacional. ESIME Unidad Zacatenco. Sección de Estudios de Posgrado e Investigación. Edificio 5, 3er piso. Unidad Profesional Adolfo López Mateos. Col. Lindavista 07738 Ciudad de México . b Comisión Nacional de Seguridad Nuclear y Salvaguardias. Dr. José Ma. Barragán No. 779, Colonia Narvarte. Del. Benito Juárez, C. P. 03020, Ciudad de México. Abstract In the case of a BWR-5, the wall of the reactor vessel located adjacent to the core is named beltline and it is subjected to neutron embrittlement, lowering the fracture toughness and increasing the yield strength of the material. Cracks can be developed in the internal surface of this area. In this paper, a semi elliptical part through thickness crack has been postulated along the axial direction. Its depth is 1.25 inch which is 0.25 of the thickness of the wall vessel and its length is 6 times the crack depth (7.5 inches). The material of the vessel is a low alloy carbon steel. In order to consider an extended period of operation, the analysis must cover sixty years of operation. The normal conditions of operation and start-up and shutdown transients have to be taken into account. For this purpose, a numerical evaluation was done with the Finite Element Method in conjunction with linear elastic fracture mechanics. This analysis was compared with the results of the procedure under the scope of the Appendix G of the ASME Code Section XI and the NUREG-0800. The results were used to establish the pressure and temperature limits. ICSI 2019 The 3rd International Conference on Structural Integrity Numerical analysis of the BWR-5 beltline region containing a crack postulated for an extended period of operation Salatiel Pérez Montejo a , Pablo Ruiz López b , Gilberto Soto Mendoza a , Alejandra Armenta Molina a , Abraham Villanueva García a , Luis H. Hernández Gómez a,* a Instituto Politécnico Nacional. ESIME Unidad Zacatenco. Sección de Estudios de Posgrado e Investigación. Edificio 5, 3er piso. Unidad Profesional Adolfo López Mateos. Col. Lindavista 07738 Ciudad de México . b Comisión Nacional de Seguridad Nuclear y Salvaguardias. Dr. José Ma. Barragán No. 779, Colonia Narvarte. Del. Benito Juárez, C. P. 03020, Ciudad de México. Abstract In the case of a BWR-5, the all of the reactor vessel located adjacent to the core is named beltline and it is subjected to neutron embrittlement, lowering the fracture toughness and increasing the yield strength of the material. Cracks ca be developed in the internal surface of this area. In this paper, a semi elliptical part through thickness crack has been postulated along the axial irection. Its depth is 1.25 inch which is 0.25 of the thickness of the wall vessel and its length is 6 times the crack depth (7.5 inches). The material of the vessel is a low alloy carbon steel. In order to consider an extended period of operation, the analysis must cover sixty years of operation. The n rmal conditions of operation and start-up and shutdown transients have to be taken into account. For this purpose, a numerical evaluation was done wit the Finite Element Method in conjunction with linear elastic fracture mechanics. This a alysis was compared with the results of the procedure under the scope of the Appendix G of the ASME Code Section XI and the NUREG-0800. The results were used to establish the pressure and temperature limits.

© 2019 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the ICSI 2019 organizers. © 2019 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the ICSI 2019 organizers. © 2019 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the ICSI 2019 organizers. Keywords: ASME Code, Beltline, BWR, Crack, Neutron Embrittlement. Keywords: ASME Code, Beltline, BWR, Crack, Neutron Embrittlement. * Corresponding author. Tel.: +52-55-57296000 ext 54762. E-mail address: luishector56@hotmail.com * Corresponding author. Tel.: +52-55-57296000 ext 54762. E-mail address: luishector56@hotmail.com

2452-3216 © 2019 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the ICSI 2019 organizers. 2452-3216 © 2019 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the ICSI 2019 organizers.

2452-3216  2019 The Authors. Published by Elsevier B.V. Peer-review under responsibility of the ICSI 2019 organizers. 10.1016/j.prostr.2019.08.017